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公开(公告)号：US4869866A
公开(公告)日：1989-09-26
申请号：US123616
申请日：1987-11-20
IPC分类号： G21C3/62
摘要： A mixture of uranium dioxide and additive of aluminosilicate composition is formed into a compact and sintered to produce a nuclear fuel wherein the uranium dioxide grains have an average grain size of at least about 20 microns and wherein substantially all of the grains are each enveloped by glassy aluminosilicate phase.
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公开(公告)号：US4942016A
公开(公告)日：1990-07-17
申请号：US245482
申请日：1988-09-19
申请人： Mickey O. Marlowe , Herman S. Rosenbaum , Trevor C. Rowland , Charles B. Patterson, Jr. , John H. Davies
发明人： Mickey O. Marlowe , Herman S. Rosenbaum , Trevor C. Rowland , Charles B. Patterson, Jr. , John H. Davies
摘要： An improved nuclear fuel element for service in power generating, water cooled nuclear reactors, comprising a fuel cladding container of an alloy of zirconium provided with a barrier lining of unalloyed zirconium metal metallurgically bonded to the container's inner surface, and enclosed therein fissionable nuclear fuel including an additive of aluminum silicate.
摘要翻译： 一种用于发电，水冷核反应堆的改进的核燃料元件，包括具有与金属结合到容器的内表面上的非合金锆金属的阻挡衬里的锆合金的燃料包层容器，并包含在其中的可裂变核燃料，其包括 硅酸铝的添加剂。
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公开(公告)号：US4869868A
公开(公告)日：1989-09-26
申请号：US124126
申请日：1987-11-23
IPC分类号： G21C3/62
摘要： A particulate mixture of uranium dioxide and additive of magnesium silicate composition is formed into a compact and sintered to produce a nuclear fuel wherein the uranium dioxide grains have an average grain size of at least about 20 microns and wherein substantially all of the grains are each enveloped with glassy magnesium silicate phase.
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公开(公告)号：US4869867A
公开(公告)日：1989-09-26
申请号：US125630
申请日：1987-11-25
IPC分类号： G21C3/62
摘要： A particulate mixture of uranium dioxide and additive of magnesium aluminosilicate composition is formed into a compact and sintered to produce a nuclear fuel wherein the uranium dioxide grains have an average grain size of at least about 20 microns and wherein substantially all of the grains are each enveloped with glassy magnesium aluminosilicate phase.
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5.发明授权
公开(公告)号：US5517540A
公开(公告)日：1996-05-14
申请号：US215457
申请日：1994-03-21
IPC分类号： G21C3/06 , B21C37/06 , C22F1/18 , F27B17/00 , G21C3/18 , G21C3/20 , G21C21/02 , G21C21/10 , G21D1/00 , G21C3/00
CPC分类号： C22F1/186 , G21C21/02 , G21C21/10 , G21C3/06 , G21C3/20 , G21C3/18 , G21Y2002/103 , G21Y2002/104 , G21Y2002/302 , G21Y2002/303 , G21Y2004/10 , G21Y2004/20 , G21Y2004/40 , Y02E30/40
摘要： A method is provided for preparing a cladding tube having an outer substrate, an intermediate zirconium barrier layer, and an inner liner. The method includes the following steps: (a) bonding an inner liner alloy sheath exterior circumferential surface to a zirconium sheath interior circumferential surface to form a barrier/inner liner sheath, and (b) bonding the exterior surface of the zirconium sheath on the barrier/inner liner sheath to the interior circumferential surface of an outer substrate alloy tube to form the cladding tube. Alternatively, the method includes the following steps: (a) bonding the zirconium sheath exterior circumferential surface to the outer substrate alloy tube interior circumferential surface to form a substrate tube/barrier sheath, and (b) bonding the exterior circumferential surface of the inner liner alloy sheath to the interior circumferential surface of the zirconium sheath of the substrate tube/barrier sheath to form said cladding tube. In either approach the tube produced by step (a) is heat treated before step (b) is performed. The bonding steps are performed by extrusion and sometimes hot isostatic pressing.
摘要翻译： 提供了一种制备具有外基板，中间锆阻挡层和内衬的包层管的方法。 该方法包括以下步骤：（a）将内衬合金护套外周表面粘合到锆护套内周表面以形成阻挡层/内衬套，以及（b）将外壳上的外壳表面粘合在屏障 /内衬套到外基板合金管的内周面，以形成包层管。 或者，该方法包括以下步骤：（a）将锆护套外周面接合到外基板合金管内周面，形成基板管/阻挡护套，（b）将内衬的外周面 合金护套连接到衬底管/屏障护套的锆护套的内圆周表面，以形成所述包层管。 在任一方法中，步骤（a）产生的管在步骤（b）执行之前进行热处理。 结合步骤通过挤出和有时热等静压进行。
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公开(公告)号：US4390497A
公开(公告)日：1983-06-28
申请号：US304011
申请日：1981-09-21
摘要： Cladding for nuclear fuel elements which is formed with a zirconium metal barrier layer bonded to the inside surface of a zirconium alloy tube and which is sized by a cold working tube reduction process and is heat treated after final reduction at a temperature and for a time period which allows substantially complete recrystallization of the zirconium metal barrier layer and provides a fine-grained microstructure therein and which stress-relieves but does not fully recrystallize the zirconium alloy tube. The crystallographic structure of the zirconium metal barrier layer may be improved by compressive deformation such as shot-peening.
摘要翻译： 形成有与锆合金管的内表面结合的锆金属阻隔层的核燃料元件的包层体，其通过冷加工管的还原工序而定，并在最终还原温度和时间段之后进行热处理 这允许锆金属阻挡层的基本上完全重结晶并且在其中提供细晶粒微结构，并且其应力消除但不完全重结晶锆合金管。 锆金属阻挡层的晶体结构可以通过诸如喷丸硬化的压缩变形来改善。
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公开(公告)号：US5517541A
公开(公告)日：1996-05-14
申请号：US240868
申请日：1994-05-10
CPC分类号： G21C3/06 , G21C3/07 , G21Y2002/103 , G21Y2002/104 , G21Y2002/302 , G21Y2004/10 , G21Y2004/20 , G21Y2004/30 , G21Y2004/40 , Y02E30/40
摘要： The present invention provides a cladding having an outer circumferential substrate, a zirconium barrier layer metallurgically bonded to the inside surface of the substrate and an inner circumferential liner metallurgically bonded to the zirconium barrier. The inner circumferential liner is more ductile than conventional Zircaloy. The low ductility of the inner circumferential liner is obtained, for example, by using a zirconium alloy containing a low tin content (e.g. less than 1.2% by weight) and/or a low oxygen content (e.g. less than 1000 ppm). The inner circumferential liner is less than about 25 micrometers thick.
摘要翻译： 本发明提供了一种具有外周基板，冶金结合到基板的内表面的锆阻挡层和与锆阻挡层冶金结合的内周衬套的包层。 内周衬套比常规Zircaloy更具延展性。 内周衬套的低延展性例如通过使用含有低锡含量（例如小于1.2重量％）和/或低氧含量（例如小于1000ppm）的锆合金而获得。 内周衬垫的厚度小于25微米。
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8.发明授权Method for making fuel cladding having zirconium barrier layers and inner liners 失效制造具有锆阻挡层和内衬的燃料包层的方法
公开(公告)号：US5383228A
公开(公告)日：1995-01-17
申请号：US91672
申请日：1993-07-14
CPC分类号： G21C3/06 , C22F1/186 , G21C21/02 , G21C21/10 , G21C3/20 , G21C3/18 , G21Y2002/103 , G21Y2002/104 , G21Y2002/302 , G21Y2002/303 , G21Y2004/10 , G21Y2004/20 , G21Y2004/40 , Y02E30/40
摘要： The present invention provides a cladding having an outer circumferential substrate, a zirconium barrier layer metallurgically bonded to the inside surface of the substrate and an inner circumferential liner metallurgically bonded to the zirconium barrier. The inner circumferential liner is more ductile than conventional Zircaloy. The low ductility of the inner circumferential liner is obtained by using a zirconium alloy containing a low tin content (e.g. less than 1.2% by weight) and/or a low oxygen content (e.g. less than 1000 ppm). The inner circumferential liner is less than about 25 micrometers thick.
摘要翻译： 本发明提供了一种具有外周基板，冶金结合到基板的内表面的锆阻挡层和与锆阻挡层冶金结合的内周衬套的包层。 内周衬套比常规Zircaloy更具延展性。 通过使用含有低锡含量（例如小于1.2重量％）和/或低氧含量（例如小于1000ppm）的锆合金，可获得内周衬套的低延展性。 内周衬垫的厚度小于25微米。
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公开(公告)号：US5223206A
公开(公告)日：1993-06-29
申请号：US894887
申请日：1992-06-08
申请人： Herman S. Rosenbaum
发明人： Herman S. Rosenbaum
摘要： An improved procedure for producing composite constructed nuclear fuel containers for service in water cooled nuclear fission reactors is disclosed. The improved production procedure maximizes the advantageous characteristics of the respective components of the composite unit. The procedure of the invention comprises heat treating the two components of a tube stock and liner stock separately prior to their assembly.
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公开(公告)号：US5524032A
公开(公告)日：1996-06-04
申请号：US215458
申请日：1994-03-21
CPC分类号： G21C3/06 , G21C3/07 , G21Y2002/103 , G21Y2002/104 , G21Y2002/302 , G21Y2004/10 , G21Y2004/20 , G21Y2004/30 , G21Y2004/40 , Y02E30/40
摘要： A cladding tube having a cross-section and including (1) a zirconium alloy outer circumferential substrate having an inner surface and having one or more alloying elements, (2) a zirconium barrier layer bonded to the inner surface of the outer circumferential substrate and being alloyed with the one or more alloying elements, and (3) a zirconium alloy inner circumferential liner bonded to the inner surface of the zirconium barrier layer. The barrier layer will have a concentration profile including a diffusion layer extending from the barrier layer's inner surface (facing nuclear fuel) to the barrier layer's interior (between the barrier layer's inner and outer surfaces). At the interior edge of the diffusion layer, there will be substantially no alloying elements. At the outer edge of the diffusion layer (the barrier layer's inner surface), the maximum concentration of alloying elements will occur.
摘要翻译： 一种具有横截面的包层管，包括（1）具有内表面并具有一个或多个合金元素的锆合金外周基材，（2）结合到外周基材的内表面上的锆阻挡层，并且 与一种或多种合金元素合金化，和（3）结合到锆阻挡层的内表面的锆合金内周衬垫。 阻挡层将具有包括从阻挡层的内表面（面向核燃料）延伸到阻挡层内部（阻挡层的内表面和外表面之间）的扩散层的浓度分布。 在扩散层的内部边缘处，基本上不存在合金元素。 在扩散层的外缘（阻挡层的内表面）处，将发生合金元素的最大浓度。
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